Thermal-Hydraulic Design of a Solid Particulate Fusion Reactor Blanket.

摘要

This paper presents the scoping thermal-hydraulics design of the Advanced Reactor Innovation Evaluation Study (ARIES-I) fusion reactor blanket that is cooled by a mixture of SiC fine particles and CO2 carrier gas. When compared to a conventional gas-cooled design, the primary advantage of this design is to greatly improve the volumetric heat capacity of the coolant, allowing lower flow velocity, pressure drops and reduced coolant pressure while maintaining the same heat transfer capability. Thermal-hydraulics parametric results and the SiC ceramic composite structured 5 atm pressure CO2 gas reference design are presented in this paper. 11 refs., 4 figs., 2 tabs.